ML20078M904

Quad-Cities Nuclear Power Station Unit One Cycle Fourteen Startup Test Results Summary

ML20078M904
Person / Time
Site:	Quad Cities
Issue date:	11/23/1994
From:	COMMONWEALTH EDISON CO.
To:
Shared Package
ML20078M880	List: ML20078M877 ML20078M904
References
NUDOCS 9412050199
Download: ML20078M904 (6)

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QUAD-CITIES NL'LLEAR POWER STATION UNIT ONE CYCLE FOURTEEN STARTUP TEST RESULTS

SUMMARY

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TABLE OF CONTENTS TEST NO.

TITLE PAGE 1

SHUTDOWN MARGIN 1

2 CORE VERIFICATION 1

3 INITIAL CRITICAL 2

4 TIP REPRODUCIBILITY 3

AND CORE POWER i

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Shutdown Marain Demonstration and Control Rod Functional Checks Purpose The purpose of this test is to demonstrate for this core loading in the most-reactive. condition during the-operating cycle, that

- the reactor can be made subcritical with the strongest control rod fully withdrawn and all other rods fully inserted.

Criteria If a shutdown margin of 0.290% ok (0.25% + R + B.C settling penalty) cannot be demonstrated with the strongest control rod fully withdrawn, the core loading must be altered to achieve this margin.

The core reactivity has been calculated to be at a maximum 0 MWD /ST into the cycle and R is given as 0.0Xok.

The control rod B,C settling penalty for Unit One is 0.04%ok.

Results and Discussion s

On July 8,1994 control rod E-5 was fully withdrawn to demonstrate that the reactor would remain subcritical with the strongest rod out. This rod was calculated by Nuclear Fuel Services (NFS) to t

have the highest worth with the core fully loaded. The strongest rod out maneuver was performed to allow single control rod withdrawals for CRD testing.

Control rod functional subcritical checks were performed as part of control rod friction testing.

No unexpected reactivity insertions were observed when any of the 177 control rods were withdrawn.

Prior to the initial critical, NFS calculated the shutdown margin to be 1.22% ok (using a critical eigenvalue of 1.004) at 0 mwd /ST, which is the point of minimum shutdown margin for the cycle (R=0).

The difference between the estimated and actual critical eigenvalue was 0.494% ok.

Corrections for temperature and period were -0.15% ok and.047% ok, respectively. Adding these corrections to the NFS calculated value, the shutdown margin for Cycle 14 was determined to be 1.517% ok.

2.

Core Verification

, Purpose The purpose of the core verification procedure is to verify proper core location and orientation for each fuel assembly.

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Criteria

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Prior to reactor startup the actual core configuration shall be verified to be ' identical to the planned core configuration.

Results and Discussion The Unit One Cycle 14 core verification was completed on July 7, 1994.

Fuel assembly orientation, seating, and serial number were verified for each assembly.

The first inspect' ion was made to verify orientation and seating of assemblies. A second pass was subsequently made to verify bundle -

serial numbers. The four assemblies in cell location 42-07 were found not to be properly seated. These assemblies were removed from the core and the fuel support piece at 42-07 was reseated.

The four assemblies were then placed back into their. proper locations and verified to be located and seated correctly. ' The 7

Cycle 14 core map is shown in Figure 1.

3.

Initial Critical Prediction Purpose The purpose of this test is to demonstrate the ability of NFS to

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calculate control rod worths and shutdown margin by predicting the in-sequence critical.

Criteria NFS' prediction for the critical rod pattern must _ agree within 1%.

Ak to the actual critical rod pattern.

A discrepancy greater than j

1% Ak will be cause for an On-Site Review and investigation by NFS.

Results and Discussion On August 19, 1994, at 1408 hours0.0163 days <br />0.391 hours <br />0.00233 weeks <br />5.35744e-4 months <br /> the reactor was brought critical with a reactor water temperature at the time of criticality ofl i

122oF. The difference between the expected critical rod pattern (at 68oF)~and the actual critical rod. pattern was 0.00894 from rod i

worth tables supplied by NFS. The temperature effect was -0.0015 Ak from NFS supplied corrections. The excess reactivity from the

-i 111 second period was 0.00047 Ak. These reactivities. sum to 1

0.00697 Ak difference (0.697% Ak) between the~ expected critical i

rod pattern'and the actual rod pattern.

This is within the 1% Ak-l criteria of this test, and NFS' ability to predict control rod t

worths is, therefore, successfully demonstrated.

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Core Power Distribution Symmetry Analysis Purpose i

The purpose of this test is to determine the magnitude of-indicated core power dist'ibution asymmetries using data (TIP r

i traces and 00-1) collected in conjunction with the CMC update.

Criteria A.

The total TIP uncertainty (including random noise and geometric uncertainties' obtained by averaging the uncertainties for all data sets) must be less than 9%.

B.

The gross check of TIP signal symmetry should yield a maximum deviation between symmetrically located pairs of less than 25%.

Results and Discussion Due to a forced shutdown, this portion of the startup test program has not been. completed. A supplement to this report will be l

issued upon completion of the test or in three months, whichever is-earliest.

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FIGURE 1 CYCLE 14 QUAD CITIES UNIT 1 REACTOR

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